Isman Mulyadi Triatmoko, Isman Mulyadi
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Dosimetry of in vitro and in vivo Trials in Thermal Column Kartini Reactor for Boron Neutron Capture Therapy (BNCT) facility by using MCNPX Simulator Code Tesalonika, Adrian; Harto, Andang Widi; Sardjono, Yohannes; Triatmoko, Isman Mulyadi
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 2 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.24246/ijpna.v1i2.63-72

Abstract

A dosimetry study of in vitro and in vivo trials system in thermal column of Kartini Reactor for Boron Neutron Capture Therapy (BNCT) facility has been conducted by using the Monte Carlo N-Particle Extended (MCNPX) software. Source of neutron originated from the 100 kW reactor which has been modified by the previous researcher. Models have been made by using simple geometries to represent tissues. Models of in vitro have been made by 4 spheres each has 1 cm diameter to represent tumour, whereas in vivo by 4 cylinders each has 6 cm length, 3 cm diameter, and breast soft tissue material with 1 cm sphere each located in the center of the cylinders to represent models of mouse with tumour. An increase in value of the boron concentration will increase the value of dose rate as well, then the exposure time should be shorter. The exposure times (in minutes) of in vitro trials for 20, 25, 30, 50, 75, 100, 125, and 150 μg boron/g tissues are 117.77, 117.77, 117.07, 115.69, 114.02, 112.39, 110.80, and 109.27. Whereas the exposure times of in vivo trials are 163.58, 162.78, 161.98, 158.88, 155.16, 151.61, 148.22, dan 144.98. In vitro trials have greater values of dose rate so that in vitro trials have shorter exposure time.
A Study of The Assessment for Boron Neutron Capture Therapy Agent Triatmoko, Isman Mulyadi; Sutjipto, Sutjipto
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.24246/ijpna.v2i1.9-19

Abstract

A study of the assessment criteria covers the synthesis and characterization of agent and test their biological effectiveness as boron neutron capture therapy (BNCT) agents in cancer treatment. The cellular uptake of this agent into the glioblastoma cells was assessed by boron analysis (ICP-MS) and by fluorescence imaging (confocal microscopy). The agent enters the glioblastoma cells exhibiting a similar profile, i.e., preferential accumulation in the cytoskeleton and membranes and a low cytotoxic activity (IC50 values higher than 200 μM). The cytotoxic activity and cellular morphological alterations after neutron irradiation in the Research Reactor (>107 neutrons cm−2 s−1) were assessed by the MTT assay and by electron microscopy (TEM). Post neutron irradiation revealed that BNCT has a higher cytotoxic effect on the glioblastoma cells. Results provide a strong rationale for considering one of these compounds as a lead candidate for a new BNCT agent.
Assessment of Analytical Instrumentation for Boron Measurement in BNCT System Triatmoko, Isman Mulyadi; Sutjipto, Sutjipto
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.24246/ijpna.v2i1.20-33

Abstract

The methods boron measurement in BNCT system has generally progressed with developments in analytical instrumentation. Spectrophotometric methods remained the methods of choice for most routine applications until the development of ICP-OES. ICP-OES was also not adequately sensitive for nutritional and medical research involving animal tissues that are naturally low in boron (B). The development of plasma-source MS (e.g., ICP-MS) not only has overcome most of these drawbacks, but also its capability of measuring B isotopes. The application of nuclear reaction methods (mainly prompt-γ spectrometry) has remained limited to some specialized fields. The validity and comparability of three different analytical techniques (QNCR, PGAA, and ICP-MS) for boron measurement in biological samples and application of these methods for examination of blood and tissue samples from a clinical study on boron uptake in blood, tissue, and neoplastic tissue, after infusion of BPA. The PET-based approach to TPS has been applied in BDTPS and a preliminary evaluation of the correct operation has been performed using a heterogeneous boron phantom, called HEBOM. The validation has been accompanied by calculations done with SERA, following the standard approach. BDTPS needs further in vivo experimental validations.
DOSE ESTIMATION OF THE BNCT WATER PHANTOM BASED ON MCNPX COMPUTER CODE SIMULATION Ramadhani, Amanda Dhyan Purna; Susilo, Susilo; Nurfatthan, Irfan; Sardjono, Yohannes; Widarto, Widarto; Wijaya, Gede Sutresna; Triatmoko, Isman Mulyadi
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 22, No 1 (2020): February 2020
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2020.22.1.5780

Abstract

Cancer is a malignant tumor that destroys healthy cells. Cancer treatment can be done by several methods, one of which is BNCT. BNCT uses 10B target which is injected into the human body, then it is irradiated with thermal or epithermal neutrons. Nuclear reaction will occur between boron and neutrons, producing alpha particle and lithium-7. The dose is estimated by how much boron and neutron should be given to the patient as a sum of number of boron, number of neutrons, number of protons, and number of gamma in the reaction of the boron and neutron. To calculate the dose, the authors simulated the reaction with Monte Carlo N Particle-X computer code. A water phantom was used to represent the human torso, as 75% of human body consists of water. Geometry designed in MCNPX is in cubic form containing water and a cancer cell with a radius of 2 cm. Neutron irradiation is simulated as originated from Kartini research reactor, modeled in cylindrical form to represent its aperture. The resulting total dose rate needed to destroy the cancer cell in GTV is 2.0814×1014 Gy.s (76,38%) with an irradiation time of 1,4414×10-13 s. In PTV the dose is 5.2295×1013 Gy.s (19,19%) with irradiation time of 5.7367×10-13 s. In CTV, required dose is 1.1866×1013 Gy.s (4,35%) with an irradiation time of 2.5283×10-12 s. In the water it is 1.9128×1011 Gy.s (0,07%) with an irradiation time of 1,5684×10-10 s. The irradiation time is extremely short since the modeling is based on water phantom instead of human body.Keywords: BNCT, Dose, Cancer, Water Phantom, MCNPX